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Showing results 1 to 15 of 15

Analysis of Rostov-II Benchmark Using Conventional Two-Step Code Systems File

Jang, Jaerim , Hursin, Mathieu , Lee, Woonghee , Pautz, Andreas , Papadionysiou, Marianna , Ferroukhi, Hakim , Lee, Deokjung

Article Issue Date2022-05 View98

Analysis of VVER-1000 mock-up criticality experiments with nuclear data library ENDF/B-VIII.0 and Monte Carlo code MCS File File

Setiawan, Fathurrahman , Lemaire, Matthieu , Lee, Deokjung

Article Issue Date2021-01 View122

Conceptual design of long-cycle boron-free small modular pressurized water reactor with control rod operation File

Jang, Jaerim , Choe, Jiwon , Choi, Sooyoung , Lemaire, Matthieu , Lee, Deokjung , Shin, Ho Cheol

Article Issue Date2020-06 View115

Cooldown procedure success criteria map for the full break size spectrum of SBLOCA File

Fynan, Douglas A. , Cho, Jaehyun , Ahn, Kwang-Il

Article Issue Date2018-01 View107

Development and validation of transient analysis module in nodal diffusion code RAST-V with Kalinin-3 coolant transient benchmark File File

Jang, Jaerim , Lee, Deokjung

Article Issue Date2024-06 View109

Development of nodal diffusion code RAST-V for Vodo-Vodyanoi Energetichesky reactor analysis File File

Jang, Jaerim , Dzianisau, Siarhei , Lee, Deokjung

Article Issue Date2022-09 View105

Effect of heat flux on the structural and chemical characteristics of fuel CRUD under pressurized water reactor primary water conditions File

Lee, Yunju , Ham, Junhyuk , Yoo, Seung Chang , Song, Inyoung , Jeong, Junhyuk , Kim, Ji Hyun

Article Issue Date2025-08 View116

Effect of oxide film on ECT detectability of surface IGSCC in laboratory-degraded alloy 600 steam generator tubing File File

Lee, Tae Hyun , Ryu, Kyung Ha , Kim, Hong Deok , Hwang, Il Soon , Kim, Ji Hyun , Lee, Min Ho , Choi, Sungyeol

Article Issue Date2019-08 View133

Machine learning of LWR spent nuclear fuel assembly decay heat measurements File File

Ebiwonjumi, Bamidele , Cherezov, Alexey , Dzianisau, Siarhei , Lee, Deokjung

Article Issue Date2021-11 View108

The DISNY facility for sub-cooled flow boiling performance analysis of CRUD deposited zirconium alloy cladding under pressurized water reactor condition: Design, construction, and operation File File

Kim, Ji Yong , Lee, Yunju , Kim, Ji Hyun , Bang, In Cheol

Article Issue Date2023-09 View120

Uncertainties of PWR spent nuclear fuel isotope inventory for back-end cycle analysis with STREAM/RAST-K File

Jang, Jaerim , Kong, Chidong , Ebiwonjumi, Bamidele , Jo, Yunki , Lee, Deokjung

Article Issue Date2021-08 View149

Uncertainty Analysis of UAM TMI-1 Benchmark by STREAM/RAST-K File File

Jang, Jaerim , Jo, Yunki , Lee, Deokjung

Article Issue Date2024-05 View146

Uncertainty quanti fi cation of PWR spent fuel due to nuclear data and modeling parameters File File

Ebiwonjumi, Bamidele , Kong, Chidong , Zhang, Peng , Cherezov, Alexey , Lee, Deokjung

Article Issue Date2021-03 View128

Uncertainty quantification in decay heat calculation of spent nuclear fuel by STREAM/RAST-K File File

Jang, Jaerim , Kong, Chidong , Ebiwonjumi, Bamidele , Cherezov, Alexey , Jo, Yunki , Lee, Deokjung

Article Issue Date2021-09 View105

Verification and validation of isotope inventory prediction for back-end cycle management using two-step method File File

Jang, Jaerim , Ebiwonjumi, Bamidele , Kim, Wonkyeong , Cherezov, Alexey , Park, Jinsu , Lee, Deokjung

Article Issue Date2021-07 View106

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